ML18025A586
| ML18025A586 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/23/1976 |
| From: | Curtis N Pennsylvania Power & Light Co |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18025A586 (5) | |
Text
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I2-76) l NRC DISTRlBUllON FoR P
AT 50 DO U.S. NUCLEAR REGULATORV COMMISSION CKET MATERIAL DOCKET NUMBER 5'0- 3'8 '7 FILE NUMBER TO:
NicC I ROM: Pa Pwr & I,i);ht Co Allentown, Pa N Il Curtis DATE OF DOCUMENT 3-23-76 DATE RECEIVED 3 2) 7I I @LETTER l
QORIGINAI QCOPV
". DESCRIPTION Qt46TORIZEO
@UNCLASSIFIED PROP INPUT FORM ENCLOSURE NUMOER OF COPIES RECEIVED one signed Ltr furnishing info concerning modificatiot to question 5.37 which will he includ'ed with material.submitted in Amdt t)16 to the PSAR.'...
T)GROT PEIIIOMf QtX)B
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'LANT NAME:
Susquehanna 1 & 2 SAFETY.
FOR ACTION/INFORMATION ENVIRO z-a~-/t) en'SSIGNED AD:
BRANCH CHIEF:
PROJECT MANAGER:
LICE SSTo e.
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noi ASSIGNED AD.
BRANCH CHIEF; PROJECT MANAGER :
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ASST'RC PDR I & E
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COLLINS HOUS'COiV PETERSON MELTZ HELTI'.iIES SKOVHOLT INTERNALD EU$ 8k E EN ~ NEERT.N KNZGIIT S IHtCEXL PAWLXCKX REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK SALTZHAN RUTBERG ISTRI BUTION BENAROYA N"
IPPOLITO OPERATING REACTORS STELLO OPERATXNG TECH E XSENIIUT SIIAO BAER SCIWENCER GRIIkES SITE SAFETY & ENVXR ANALYSXS DENTON & MULLER ERNST ALLIIIRD SPANGLER SITE TECH GAIIMXLL STEPP HUI2IAN SITE ANALYSXS VOLLEY IER BUNCH J,
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March 23, 1976 p REGULATORY DOCKET Fli F COPY Director of Nuclear Reactor Regulation Light Water Reactors Branch No. 1-2 U. S. Nuclear Regulatory Commission Washington, DC 20555 PP8,IL TWO NORTH NINTH STREET, ALLENTOWN, PA.
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Attention:
Dr. Walter R. Butler, Chief SUSQUEHANNA STEAM ELECTRIC STATION MODIFICATION TO QUESTION 5.37 ER 100450 FILE 840-2 PLA-110 cket Nos.
50-387 50-388 44 S
Dear Dr. Butler:
cS'e are in the process of writing our Stru Zg ity Test Procedure to be submitted. to you in late April, 1976.
In Amen ent
- 15116, we submitted an amended response to Question 5.37 on compliance with Regulatory Guide 1.18.
This response listed our exceptions to Regulatory Guide 1.18.
We have two additional exceptions.
They are as follows:
l.
Reference:
Paragraph C.2 of the Regulatory Guide.
We intend to select the number and distribution of measuring. points for monitoring radial deflections so that the as-built conditions can be considered in the assessment of general shell response.
In general the locations of measuring points for radial deflections are in agreement with Figure B, except point 1.
Point 1 is provided at a distance of two times the wall thickness (12') from the base slab:
This variation is made to properly predict the containment behavior near the base slab to wall connection.
If point 1 were t'obe provided at a height of three times the wall thickness (18') it would be located very close to point 2 (suppression chamber wall midheight is 26') and would not yield any additional behavior pattern of the containment.
2.-
Reference:
Paragraph C.5 of the Regulatory Guide.
Because of the current state of the art, triaxiel concrete strain distortion measurements, while
- taken, may not be used to evaluate the containment strain distribu-tion.
The concrete strain will be evaluated using linear strain measurements in the meridional and radial directions.
3112 PENNSYLVANIA POWER IL LIGHT COMPANY
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Page 2
March 23, 1976 As we stated before, we intend, to "submit our Structural Integrity Test Procedure in late April and. would. like your comments on these exceptions prior to that d.ate
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N.
W. Curtis Vice President-Engineering 5 Construction NWC:AAW